TEM examination of phases formed between U–Pu–Zr fuel and Fe
Source abstract
Abstract
Abstract Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between U–22Pu–4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel cladding chemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe 2 U (Fd-3m), FeU 6 (I4/mcm), Fe 2 Zr (Fd-3m), FeZr 2 (I4/mcm), Fe 2 Pu (Fd-3m), UZr 2 (P6/mmm), β-Zr (Im-3m), and ZrO 2 (Fm-3m).
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (20)
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